ML20246J779

Application for Amends to Licenses DPR-29 & DPR-30,revising Tech Specs to Allow Loop B of RHR HXs on Each Unit to Be Fed from RHR C & D Svc Water Pumps on Unit 1 Via cross-tie Line

ML20246J779
Person / Time
Site:	Quad Cities
Issue date:	08/28/1989
From:	Stols R COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20246J784	List: ML20246J779 ML20246J796
References
0265T, 265T, NUDOCS 8909050259
Download: ML20246J779 (2)

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Commonwealth Edison dfdic *[ 72 West Adams Street, Chicago, llhnois M

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. Nd( ._Chicago, x[ X6 dress PTply to: Post office Box 767-Ilhnois 60690 - 0767

[ August 28,.1989

'g Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission-

. Washington, DC 20555

Subject:

Quad Cities Station Units 1 and 2 Application for Amendment to Facility-Operating License DPR-29 and DPR-30 Appendix A, Technical Specifications NRC Docket Nos. 50-254 and 50-265 References (a): R..Stols letter to T.E. Murley dated March 31, 1989.

(b): R. Stols letter to T.E. Murley dated August 7,:1989.

(c):- Safety Evaluation by the Office of Nuclear

-Reactor Regulation Supporting Amendment 75 to Provisional Operating License No. DPR-29 and Amendment 68 dated Decensber 18, 1981.

Dr. Murley:

Pursuant to 10 CFR 50.90, Commonwealth Edison Company proposes a temporary change to Appendix A, Technical. Specifications to Facility Operating Licenses DPR-29 and DPR-30 for Quad Cities Units 1 and 2, respectively. The purpose of the change is to allow the "B" loop of the Residual Heat Removal (RHR) heat exchangers on each unit to be fed from the.RHR "C" and "D" service water pumps on Unit i via the cross-tie line. The "A" loop on each unit will remain unchanged.

On Sunday, August 27, 1989, the Unit 2 "C" and "D" RHR Service Hater pumps failed to meet the' required flow rates specified in Technical Specification Section 4.5.B.1.b. It is believed that the cause of this-failure was further deterioration of the Unit 2 "B" RHR Service Hater loop pipe crack surmised in March, 1989. A similar Technical Specification amendment was prepared in Reference (a) and was subsequently withdrawn in Reference (b).. .The proposed amendment was withdrawn with the concurrence of NRR since further deterioration of the crack was not evident based on weekly surveillance performed since March 13, 1989.

The proposed. changes are listed in Attachment 1 and further described in Attachments 2 and 3. Figures 1 and 2 provide pictorial representation of the system configuration and the electrical distribution systam for your reference. goof 8909050209 890828 I PDR ADOCK 05000254 i P PDC I

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., Dr. T.E. Murley - August-28, 1989 r

The proposed' changes have~been reviewed and approved by.both On-Site and Off-Site review in accordance with Commonwealth Edison Company's procedures. These proposed amendments have been reviewed in accordance with 10 CFR 50.92(c)'and determined that no significant hazards consideration exists. This evkluation is documented in Attachment 4.

Commonwealth Edison believes that this proposed Technical Specification meets the criteria established in 10 CFR 50.91(a)(5) and requests emergency approval of this proposed amendment. The basis for this determination is documented in Attachment 5.

A-similar Technical Specification change was proposed and approved by the NRC in December, 1981 (Reference (c)). The Safety Evaluation for the amendments is contained in Attachment 6 for your reference.

Commonwealth Edison is notifying the State of Illinois of our application for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.

Please direct any questions you may have regarding this matter to this. office.

Very truly yours,

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R. Stols Nuclear Licensing Administrator im Attachments 1: Proposed Changes.to Appendix A Technical Specifications for Quad Cities 1 and 2 2: Summary of Changes 3: Description and Bases for Amendment Request 4: Evaluation of No Significant Hazarjs 5: Justification for Emergency Approval of Proposed Technical Specification Amendment 6: Safety Evaluation dated December 18, 1981 Figure 1: Crosstie of RHR Service Water System Figure 2: Quad Cities RHR Service Water Pumps Electrical Distribution System cc: Regional Administrator - Region III Office of Nuclear Facility Safety - IDNS D. Muller - NRR B.L. Siegel - Project Manager, NRR Region III Inspector - Quad Cities 0265T:2

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